ML18092B335
| ML18092B335 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/28/1986 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8610310025 | |
| Download: ML18092B335 (24) | |
Text
Octobe.8, 1986 Docket No. 50-272 MEMORANDUM FOR:
Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing-A FROM:
Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B
SUBJECT:
PROPOSED LICENSE CONDITION, SAFEGUARDS SER INPUT AND UP-TO-DATE FACILITY ATTACHMENT - SALEM NUCLEAR GENERATING STATION, UNIT 1 Salem Unit 1 was selected from the U.S. Eligible List, by the International Atomic Energy Agency (IAEA) under Article 39(b) of the US/IAEA Safeguards Agreement for the application of IAEA Safeguards, effective January 1, 1986.
Enclosed are a proposed License Condition, a Safeguards SER input and an up-to-date Facility Attachment for Salem Unit 1.
The approved Design Information Questionnaire, submitted by the licensee, was used for the generation of the Facility Attachment which was prepared by the U.S. Negotiating Team and the IAEA Technical Review Group.
The License Condition was developed for, and in conjunction with, the licensee for the purpose of clarifying the intent of certain portions of the Facility Attachment.
The Facility Attachment and License Condition should be issued to the licensee as soon as possible.
We understand that the requirements of the 11Sholly Amendment 11 have been satisfied.
Enclosures:
Original signed by Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B
- 1.
Proposed License Condition
- 2.
SER Input
- 3.
Finalized Facility Attachment cc w/enclosures:
D. Fischer (3)
M. Rushbrook CONTACT:
J. Gibson, PBSS Ext. 28280 A~:ac ~son
\\!j~/86 4-iO!tV{/86 cc w/o enclosures:
W. B. Brown R. Jackson C. Buracker d?ow lO/)t/86 8610310025 861028 PDR ADOCK 05000272 F
PDR DISTRIBUTION:
Docket File NRG PDR Local PDR PBSS Rdg.
PNoonan JGibson OLynch HBerkow
Docket No. 50-272 MEMORANDUM FOR:
FROM:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 2_8, 1986 Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing-A Herbert N. Berkow, Director Standardization and Special Projects. Directorate Division of PWR Licensing~B
SUBJECT:
PROPOSED. LICENSE CONDITION, SAFEGUARDS SER INPUT AND UP-TO-DATE FACILITY ATTACHMENT - SALEM NUCLEAR GENERATING STATION, UNIT 1 Salem Unit 1 was selected from the U.S. Eligible List, by the International Atomic Energy Agency (IAEA) under Article 39(b) of the US/IAEA Safeguards.
Agreement for the application of IAEA Safeguards, effective January 1, 1986.
Enclosed are a proposed License Condition, a Safeguards SER input and an up-to-date Facility Attachment for Salem Unit 1.
The approved Design Information' Questionnaire, submitted by the licensee, was used for the generation of the Facility Attachment which was prepared by the U.S. Negotiating Team and the IAEA Technical Review Group.
The License Condition was developed for, and in conjunction with, the licensee for the purpose of clarifying the intent of certain portions of the Facility Attachment.
The Facility Attachment and License Condition should be issued to the licensee as soon as possible.
We understand that the requirements of the "Sholly Amendment" have* been satisfied.
Enclosures:
??~
erbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B
- 1.
Proposed License Condition
- 2.
SER Input
- 3.
Finalized Facility Attachment cc w/enclosures:
D. Fischer (3)
M. Rushbrook CONTACT:
J. Gibson, PBSS Ext. 28280 cc w/o enclosures:
W. B. Brown R. Jackson C. Buracker
Docket 50-2-72 Enclosure Safeguards Safety Evaluation Report - Salem Nuclear Generating Station, Unit.! (~NTirfY Salem was chosen by the International Atomic Energy Agency (IAEA), from the U.S. Eligible List, to come under the US/IAEA Safeguards Agreement.
The required Design Information Questionnaire (DIQ) dated October 10, 1985 was submitted.by Salem to provide a description of their current operations and material control and accounting procedures. The review criteria used for review of the DIQ was the document:
"Instructions for Completing IAEA DIQ - Power Reactors," (IAEA Form N-71/Revision I - November 1976 and IAEA Form N-72/Revision I - April 1977} USNRC June 1980.
The completed and approved DIQ is necessary for the generation of the Facility Attachment as prepared by the U.S. Negotiating Team and the IAEA Technical Review Group.
The final approved Facility Attachment must be incorporated as a condition of license in order to implement the provisions of the US/IAEA Safeguards Agreement at the Salem Nuclear Generating Station Unit 1.
IAEA Safeguards
Enclosure Salem Nuclear Generatinr Station, Unit 1 (SNGS 1)
IAEA Safeguards icense Cona:rtTons
~
- 1.
Incorporation of Facility
Attachment:
0 Pursuant to 10 CFR 75.8, NRC License No. DPR-70 is hereby amended to incorporate by reference Codes 1. through 7. of Facility Attachment No. 13 dated October 1, 1986, to the US/IAEA Safeguards Agreement.
- 2.
Facility Attachment Code 7.9 The specific facility health and safety rules and regulations to be observed by the Agency's (IAEA) inspectors, as specified in Paragraph 54 of the design information as of October 10, 1985, provided by the USA mean:
0 0
0 0
Agency inspectors who have previously visited the facility will be informed as necessary at the time of entry into the facility of health and safety rules and ad hoc rules as might be required in view of a special situation that liasliCcurred at the facility since the inspectors' last visit to the facility. The briefing will be of a short duration, not to exceed 30 minutes, covering topics deemed relevant by the licensee.
Agency inspectors who have not previously visited the facility will be informed as necessary at""""'tfie time of entry into the faci 1 i ty of health and. safety rules and ad hoc rules as might be required in view of a special situation that hasliCcurred at the facility.
The briefing will be of an appropriate duration, not to exceed three hours, and consist of topics deemed relevant by the licensee.
In either case, the licensee should take into account the Agency inspector's prior training, expertise and experience.
In neither case shall the Agency inspector be subject to any form of evaluation or testing by facility representatives or representatives of the U.S.
Government.
For health and safety reasons, Agency inspectors will be escorted by qualified facility personnel at times deemed appropriate by the licensee.
- 3.
Termination:
0 Pursuant to the provisions of 10 CFR 75.41, the ColTDllission will inform the licensee, in writing, when its installation is no longer subject to Article 39(b) of the principal text of the US/IAEA Safeguards Agreement.* The IAEA Safeguards License Conditions incorporating Code 7. of the Facility Attachment as part of NRC License No. DPR-70 will be terminated as of the date of such notice
l..
from the Commission.
However, since the IAEA may elect to*maintain the licensee's installation under Article 2(a) of the Protocol, provisions equivalent to Codes 1. through 6. of the Facility Attachment (with possible appropriate modifications) may still apply, and accordingly all other IAEA Safeguards License Conditions to NRC License No. DPR-70 will remain in effect until the Commission notifies the licensee otherwise. If this option is not selected by the IAEA, the Commission will then notify the licensee that all License Conditions pertaining to the US/IAEA Safeguards Agreement are terminated.
UNCLJ\\SSlf lED prepared on 1986~9-24 Date of e~ into force:
Text 1986-10-01 Safeguards Agreement between USA and the IAEA Subsidiary Arrangements Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Coda: UXHF I MBA Code: UXHF Total number of pages:
19 Code
- 1.
1.1
- 1. 2
- 1. 3
- 1. 4
[0609W]
General Part Reference Codes Agreement Reference (Articles) 43(a)
Page No. 1 of 19 pages SAFEGUARDS CONFIDENTIAL Identification of the facility Facility identification code: UXHF Salem Nuclear Generating Station Unit 1 (SNGS 1)
Owner and Operator Public Service Electric & Gas Co.
Geographic location Salem County, New Jersey, USA Postal address Public Service Electric and Gas Co.
Nuclear Department P.Q. Box 236 Hancocks Bridge, New Jersey 08038 Description The power station consists of one pressurized light water reactor.
Pin removal or exchange is not normally performed.
Main design features are as follows:
- Reactor thermal output:
3411 rt.+J(th)
- Refuelling interval:
normally 15-19 months
- Number of fuel assemblies in the reactor core: 193
- Fresh fuel storage capacity:
72
- Spent fuel storage capacity:
1170
i~
Text prepared on Date of e 1ly into* force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA Code: UXHF Code General Part Reference (Codes) 1.4 (continued}
1.5 2..
3.1
- 2. 1 2.2 3.1. 3 Agreement Reference (Articles) 43, 44 46(a}
8(c}
45 Page No. 2 of 19 pages SAFEGUARDS EONFIDENTIAL
- Nominal weight of nuclear material in an assembly:
462kg
- Maximum fresh fuel enrichment (U-235):
3.80 w/o
- Number of assemblies normally discharged on refuelling:
72-117 Maps and plans See Design Information Questionnaire (DIQ).
Infonnation on the facility This facility attachment is based on the design information dated 10 October 1985, and the design information supplement provided in September 1986.
Location of information Identical sets of the information provided on the facility are kept.at the Agency, at the facility and at the USNRC Headquarters.
Changes in the information on the facility to be provided in advance With reference to the relevant paragraphs of the Design Information Questionnaire
- Change in the rated thermal output for continuous operation by 20~ or more; (14}
- Change of the type of fuel used, e.g.
introduction of mixed oxide fuel for test purposes or for routine use; (22, 23, 25}
- Change of the maximum enrichments of the fuel; (23)
- Change in the design of the reactor fuel; (24, 26, 27}
Installation of equipment for pin removals or exchange in assemblies for test purposes or for routine use; (13, ZS)
- Change in the method and/or procedure of identifying individual fuel assemblies; (31)
- Change in the methods and/or equipment for refuelling and/or for handling of irradiated fuel; (41)
- I Text prepared on Date of ely into force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA Code: UXHF Page No. 3 of 19 pages Code General Part Reference Codes 2.2 (continued)
- 3.
' 3. 1 3.1.1 3.1. 2 Agreement Reference (Articles) 29 46(b) 46(b) 90(1<)
SAFEGUARDS EONFIDENTIA~
- Change influencing the access to the reactor vessel and/or its cover; (43)
- Change in the number of fuel assemblies, control elements, dummy assemblies and/or irradiation positions inside the reactor vessel; (44)
- Change in the method of storage of irradiated fuel and/or in the spent fuel storage capacity; (48)
Installation of any dismantling, decladding or dissolution equipment; (13, 28, Sl)
- Change in the nuclear material accountancy and control procedures; (SS}
- Change in the access routes to the reactor area; (10)
Change in the shipping containers and/or the routes followed by irradiated fuel within the facility; (SO)
- Change in the health and safety rules and
.procedures affecting the conduct of inspection; (S4)
Any change in other parts of the design information to be submitted when the change has been completed.
Safeguards measures Accountancy Material Balance Areas and their identification codes.
The Salem Nuclear Generating Station Unit 1, UXHF, constitutes one material balance area, UXHF.
Strategic points which are Key Measurement Points (KMPs), (for their specifications see Code 4.)
(a) For determination of nuclear material flow:
KMP 1 - Receipts, accidental gains and de-exemption of nuclear material;
'I Text prepared on e
Date of entry into force:
198~10--01 Facility Attachment No. 13 Facility~Code: UXHF'/ MBA Code: UXHF SALEM NUCLEAR GENERATING STATION, UNIT 1 Code
. General Part Reference Codes 3.1.2 (continued) 3.1. 3 3.2 3.2.1 Agreement Reference (Articles) 46(c) 29 46(f) 90(S)
Page No. 4 of 19 pages SAFEGUARDS CONFIDENTIAL KMP 2 - Nuclear loss (burn-up) nuclear production and category change in fuel discharged from the reactor; nuclear loss (Pu-241 decay);
KMP 3 - Shipments of nuclear material, withdrawals, exemptions and accidental losses; (b) For determination of physical inventory:
KMP A - Fresh fuel storage and inspection area; KMP B - Reactor core; KMP C - Spent fuel storage racks and spent fuel shipping casks; KMP D - Other locations of nuclear material at the facility.
Physical inventory taking Nominal timing:
As soon as possible after completion of each refuelling and before the reactor is closed again.
In cases of prolonged shutdowns of one year or longer, PITs shall be performed once every twelve months.
Procedures:
Item counting and identification.
Preparation of itemized list of nuclear material including identification number, material description, quantity of nuclear material and location of each item for each inventory KMP.
Containment and surveillance Strategic points for application of containment and surveillance measures
- Reactor hall including reactor vessel;
- Access routes to and from the reactor hall and spent fuel pool;
- Fresh and spent fuel storage areas; Any other points that might be mutually agreed.
- I Text prepared on e UNClASSIFIED 1986-09-24 f e.
Date o entry into force:
1986-10-01 Facility Attachment No. 13 Facility_Code: UXHF *; MBA Code: UXHF SALEM NUCLEAR GENERATING STATION, UNIT 1 Code 3.2.2 3.3 3.4 3.5 General Part Reference Codes 6.1 6.2 3
- 7 I 7
- 1 Agreement Reference (Articles) 73(d) 73(e) 11, 35 36, 37 12(a)
Page No. 5 of 19 pages SAFEGUARDS CONFIDENTIAL Installed Agency instruments and devices (a) Seals to ensure the containment of the reactor vessel; (b) Cameras for surveillance of fuel movements into or out of the reactor vessel, the reactor containment and the fresh and spent fuel storage areas; (c) Seals on shipping casks with spent fuel and other containers as applicable; (d) Seals on Agency instruments and devices; (e) Seals on containers with fuel a~sembli~~
- received at the facility; (f) Seals on the reactor containment building (e.g.
equipment hatches).
If there is a need to break a seal or interfere with the operation of surveillance devices, the Agency shall be informed in advance and by the fastest means.
This information shall include the (probable) date on which the operation will take place.
Specific prov1s1ons and criteria for termination of safeguards on nuclear material l\\lone.
Specific prov1s1ons for exempting nuclear material from safeguards None.
Specific prov1s1ons and criteria for withdrawal of nuclear material from safeguards None.
UNCU\\JSlf 1 tO Te1<t prepared on 1986-09-"'
SAFE6UARBS ce10ENTIAL Date of entry i o force:
1986-10--01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA* Code: UXHF I
Page No. 6 of 19 pages Code 4.
Code 4.1:
KMPs for the flow of nuclear material I
I I
I I
I I
Kl Ml e.1 I
1 Inventory Change Receipts of nuclear material Description of a typical I
!Mat.
Meas. I
~'
Source data IDescr. basis!
batch item '------------Code __ I I
I For fuel assemblies:
One I For each fuel assembly:
BQ2F N I fuel I I
One fuel assembly.
assem-1 1) Identification number; I
bly I 2) Weights of total and I
I fissile uranium, and I
I the chemical composi-I I
tion; I
I based on shipper's data.
I
___ I ____________ --- __ I For small quantities of nuclear material (each less than 0.01 effective kilogram):
A number of such quanti-1 ties received in one I
calendar month from the I same shipper or, if*a physical inventory was taken during the month, I
I I
separately before and I
after the time of physi-1 cal inventory taking.
I I
I As I For each batch:
As I
N appro-1 priate 1) Weight of compound;
- 2) Weights of total and fissile uranium, and of plutonium, and the chemical composition; based on shipper's data.
appro-priate
_____________ I _____ ---------------~ ----
De-exemption, Accidental gain Same as for Receipts at KMP 1 above.
I 12 Nuclear For fuel assemblies:
One I
I fuel I jassem-1 I bly I
For each fuel assembly:
BQlG M
I I
I I
I I
I production, Nuclear loss (burn-up)
One fuel assembly.
I I
I I
I I
I I
1)-2) As for fuel assem-blies at KMP 1 above;
- 3) Date of discharge;
- 4) Estimated burn-up of each fuel assembly (in MWD/tu);
BQ4G M
I__._ _________ _._ ___________________ _._ __ ~~------------------'------'--~
e Text prepared on 1986-09-24 SAFEGUARDS C9NFl,TIAL UNCLASSIFJED Date of entry in o force:
1986-10--01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: _UXHF I MBA *code: UXHF Page No. 7 of 19 pages Code 4.1:
Nuclear Material Flow KMPs I
I
.....,-------~---:-~--=--------------:~--:---'
Kl Description of a typical
!Mat.
Meas. I Ml Inventory Source data IDescr. basis!
PI Change batch item ____________ I Code
__ I I
I I
21 Nuclear
- 5) Nuclear loss of total I I
I production, and fissile uranium I
I I Nuclear loss and nuclear production I
I (burn-up) of total plutonium I
I when calculated, I
I [continued]
including as of the I
I I date of discharge. )J I
-'~-------- ------------------- --- ---------------------- --- __ I 3
Category change For fuel assemblies:
One fuel assembly One fuel ass em-I
. bly I
I
- 1) Identification number;
- 2) Date of discharge;
- 3) Weight of total and fissile uranium as of the date of discharge.
BQlG M
~------- ---------------- ___ I~-------------~ ---
Nuclear loss (Pu-241 decay)
For fuel assemblies:
One fuel assembly.
1 One I
fuel I assem-bly For each fuel assembly:
1)-2) As for fuel assem-blies at KMP 1 above;
- 3) Date of discharge and shipment;
- 4) Nuclear loss of total plutonium (Pu-241 decay) for each fuel assembly when calcu-lated, including as of the date of shipment.
BQlG M
BQ4G M
I
~-------- --------------- --- -------------------- --- __ I Shipment of nuclear material For fuel assemblies:
One fuel assembly.
I One For each fresh fuel BQ2F N I fuel assembly:
I ass em-I I
bly I 1) Identification number; I
I 2) Weights of total and I
I fissile uranium, and I
I the chemical composi-I I
tion.
I
~------- --------------- ___ I ____________ ~ ______ I 1/ If fuel assemblies discharged from the reactor are returned to the core, the values for nuclear production and nuclear loss which had been recorded for these assemblies shall be kept.
Text prepared on 1986-09-~
SAFES HAlrn5 ~UN~ IUl~ IAL UNQ.ASSIFIED Date of entry into force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA.Code: UXHF Page No. 8 of 19 pages I
I I Code 4.1:
Nuclear Material Flow KMPs I
l------~~-----:------~---------~--.,...---1 I KI Description of a typical I
Mat.
I Meas. I IMI Inventory
- I Source data Descr. I basis I I.el Change batch item I ___________ Code l __ I I I I I I
13 Shipment of For fuel assemblies:
One I For each irradiated fuel BQ2G M I nuclear I fuel I assembly:
I*
material One fuel assembly.
lassem-I
[continued]
I bly
- 1) Identification number; I
I
- 2) Date of discharge; I
I
- 3) Burn-up (~D/tU);
I I
- 4) Weights of total and I
fissile uranium and I
of total plutonium, I
calculated as of the date of discharge, and corrected for Pu-241 decay between the datel of discharge and the I
. 5) date of shipment; I
Isotopic composition I
of uranium and pluto-I nium calculated for I
each assembly as of I
the date of discharge, I and corrected for I
Pu-241 decay between I
the date of discharge and the date of ship-ment.
I
--- ----------------------- --- ___ I For small quantities of nuclear material (each less than 0.01 effective kilogram):
For each batch:
As appro-1 priate I 1)
I 2)
I Any number of such quan-1 I
tities shipped in one I
I calendar month to the I
I same recipient or, if a physical inventory was taken during the month, I
I I
I I
I Weight of compound; Weights of total and fissile uranium, and of plutonium, and the chemical composition.
As N,
appro-M priate separately before and I
I I
after the time of physi-1 I
I cal inventory taking.
I I
I
______________________ l ____ I _______________________ --- ___ I Exemption Accidental loss/
Withdrawal Same as for Shipment at KMP 3 above.
I I
I I
I I
I
Text prepared on 1986-09-'
SAFEGUARDS CBNFIMNTIAL UNG~IE.O Date of entry i o force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA*Code: UXHF Page No. 9 of 19 pages I
I I Code 4.2:
KMPs for the physical inventory of nuclear material I
'-~~~~~~~~~~~~~~--:~~~~~~~~~~~~~~~~~I I KI Description of a typical I
I Mat.
I Meas. I IMI I
Source data IDescr.lbasisl I Pl batch item I I Code l __ I I I I
I I
I I A For fuel assemblies:
One I For each fuel assembly:
I BQlF I N I I
fuel I I BQ2F I N I I
One fuel assembly.
assem-1 As for fuel assemblies at I
I I
I bly I KMP 1 above.
I I
I I_
I I
'~~I B For fuel assemblies:
One. fuel assembly.
I I
I I
One I As for fuei assemblies at KMP ll BQ4F I N I fuel I for unirradiated fuel or as forl BQ4G I M I assem-1 fuel assemblies at KMP 2 on I
I I
bly I calculated values for I
I I
I irradiated fuel.
I I
I
~-------------------------- _____ 1 ___________________________ 1 _____ 1 __ 1 I
I I
I C For fuel assemblies:
One I For each fuel assembly:
I BQlG I M One fuel assembly.
I Al For small quantities of nuclear Bl material (each less than 0.01 Cl effective kilogram):
DI I Any number of such quantities.
fuel I I BQ2G I M
assem-
- 1) Identification number; I
bly
- 2) Weights of total and fissile As appro-1 priatel I
I uranium and of total pluto-nium calculated as of the date of discharge, and corrected for Pu-241 decay between the date of dis-charge and the date of shipment;
- 3) Date of discharge; 4)'Burn-up (MWD/tU);
- 5) Isotopic composition.
For each batch:
- 1) Weight of compound;
As appro-1 priatel I
I N,
M
e UNCLASSIF'ED e
Text prepared on 1986-09-24 Date of entry into force:
1986-10-01 Facility Attachment No. 13 Facility~Code: UXHF J MBA Code: UXHF SALEM NUCLEAR GENERATING STATION, UNIT 1 Code
- 5.
5.1
- 5. 1. 1 5.1.2 General _
Part Reference Codes 6.3,6.2 3, 7 I 7, 1 2.1 Agreement Reference (Articles)
Page No. 10 of 19 pages SAFEGUARDS CONFIDENTIAL Records system Specific provisions for accounting records Inventory changes (for.the specifications of source data see Code 4.1 above), time of recording.
- Receipt:
Upon receipt.
- Nuclear loss (burn-up), nuclear production and category change:
When calculated, including upon discharge. 2/, !/
- Nuclear loss (Pu-241 decay):
When calculated, including upon shipment.
- Shipment:
Upon shipment.
- Exemption/de-exemption:
Upon acco'unting transfer of the nuclear material.
- Accidental loss/gain:
Upon establishment of the amount of material lost/gained.
- Withdrawal:
Upon withdrawal.
Measurement (item counting and identification) results used for determination of the physical inventory (for specifications of source data see Code 4.2 above), time of recording.
- Itemized list of nuclear material quantities on inventory for each inventory KMP:
Upon identification and counting of items during the physical inventory taking.
- Itemized list of nuclear material inventory identifying changes since the physical inventory taking:
Before inventory verification.
~/ Fuel removed from the reactor shall be considered as discharged if it remains out of the core after the routine refuelling shutdown is completed.
~./ If fuel assemblies discharged from the reactor are returned to the core, the values for nuclear production and nuclear loss which had been recorded
~NCLASSlf IED e
Date of entry into force:
1986-10-01 Text prepared on 1996-09-24 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility _Code: UXHF I MBA Code: UXHF Code 5.1.3 5.2 5.2.-1 5.2.2 5.2.3 General Part Reference Codes Agreement Reference (Articles)
Page No. 11 of 19 pages SAFEGUARDS CONFIDENTIAL Adjustments and corrections, time of recording.
- Shipper/receiver difference:
Normally not relevant.
MUF:
Normally identical to zero.
Corrections:
Whenever errors have been found, with specific reference to the entry being corrected.
Specific provisions for operating records Operating data used to establish changes in the quantities and composit~on of nuclear material
- Location of each fuel assembly at any time;
- The relevant source data with respect to nuclear loss and production, including:
(a) The monthly integrated thermal power produced by the reactor; and (b) The estimated burn-up On r-wD/t of uranium) for each fuel assembly;
- Date and duration of any reactor shutdown;
- Date and nature of the use of fuel handling and transport equipment.
Calibrations Not required.
Sequence of the actions taken in preparing for and in taking the physical inventory
- All physical inventory KMPs:
Dates and description of the actions taken and the results obtained.
An itemized list of nuclear material inventory after completion of inventory taking by the operator but before commencement of verif~cation by the Agency.
UNCLASSlflED Text prepared on 198"09-24 Date of e"ry into force:
1986-10-01 Facility Attachment No. 13 FacilitY:_Code: UXHF"/ MBA Code: UXHF SALEM NUCLEAR GENERATING STATION, UNIT 1 Code 5.2.4 5.3 5.4
- 6.
6.1 6.1.1 6.1.2 6.2 6.2.1 General Part Reference Codes 3.4.1 10 3.4.1 Agreement Reference (Articles) t
~:*.*
-~
~,*
~,,
-~>'
62 62(a)
Page No. 12 of 19 pages SAFEGUARDS 60NFIDENTIAL' Actions taken in order to ascertain the cause and magnitude of any accidental or unmeasured loss
- Dates and description of the actions taken and the results obtained.
Location and language of records At the facility in English.
Retention period for records Five years.
Reports system Specific provisions for Inventory Change Reports*
(ICRs)
Contents The recorded entries to be reported are those types specified in Code 5.1.1 above.
ICRs will be completed as specified in the relevant paragraphs of Code 10, General Part.
Nuclear loss, nuclear production.and category change for irradiated fuel assemblies will be reported when calculated including as of the date of discharge.
Timing or frequency of dispatch As soon as possible and in any event within 30 days after the end of the month in which inventory changes specified in Code 5.1.1 occu~red or were established.
Specific provisions for concise notes Concise notes explaining the inventory changes
- To be attached to ICRs containing data on nuclear loss and production; they are to state the burn-up in MWD/t of initial U for each fuel assembly discharged;
. r UNCLASSIFIED
. Text prepared on 1986,9-24 Date of en'y into force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA Code: UXHF Code General Part Reference (Codes) 6.2.1 (continued) 6.2.2 6.3 3.4.2 6.3.1 10 6.3.2 10 Agreement Reference (Articles) 61(b},6S 65~ 90(M)
Page No. 13 of 19 pages SAFEGUARDS CONFIDENTIAL
- To be attached to ICRs to explain unusual inventory changes (such as accidental loss) and corrections.
They may also be used to explain any other part of information included in reports.
Concise notes describing the anticipated operational programme; subject and time of dispatch.
- Planned operations involving refuelling, fresh fuel receipts and spent fuel shipments:
To be attached to each MBR (see Code 6.3.3 below) and to cover the period until the end of the next refuelling, to be updated every six months.
- Precise forecasts for:
a)
Date of the next refuelling, physical**
inventory taking including date when seals are expected to be removed from the reactor; and b)
Spent fuel shipments, including information about the shipping casks to be used, the extent to which they are expected to be filled:
to reach the Agency at least 30 days in advance, subsequent changes as soon as known.
Specific provisions for Material Balance Reports (MBR)
MBR contents The consolidated inventory changes to be reported are those types specified in Code 5.1.1 above.
MBRs will be completed as specified in relevant paragraphs of Code 10, General Part.
PIL contents
- Physical inventory listings (PILs) based on the results of physical inventory taking, to be attached to MBRs. The batch data included in PILs will be based on the shipper's data on the initial nuclear material content for the fuel for unirradiated fuel assemblies or on the operator's data for irradiated fuel assemblies.
PILs will be completed as specified in relevant paragraphs of Code 10, General Part.
UNCLASSlFIED Text prepared on 199~9-24 Date of ely into* force:
1986-10-01 Facility Attachment No. 13
,SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA Code: UXHF Code 6.3.3 6.4 6.4.1 6.4.2 General Part Reference Codes 3.5.1 Agreement Reference (Articles)
Page No. 14 of 19 pages SAFEGUARDS CONFIDENTIAL Timing or frequency of dispatch:
As soon as possible and in any event within 30 days after the physical inventory taking under Code 3.1.3 above..
~lffl'} Special reports Specification of incidents or circumstances requiring submission of special reports (a) Losses:
One or more fuel assemblies; (b) Changes in containment:
- Physical integrity of a fuel assembly as an accounting unit is accidentally broken; Any Agency containment and surveillance device, referred to in Code 3.2.2 is interfered with or removed in the absence of Agency inspectors, unless the Agency has been informed in advance as provided.4/
Contents
- Date when"the incident occurred or circumstances were established;
- Description of the actions taken in order to ascertain the cause of the event and to establish the magnitude of any loss of nuclear material;
- Cause and features of the incident or circumstances; 11 In respect of seals on shipping casks, this requirement applies only while the cask remains in the facility.
Text prepared on Date of en"y into force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA Code: UXHF Code 6.4.2
- 7.
7.1 7.2 7.3 7.4 7.4.1 7.4.2 General Part Reference Codes (continued) 4.2 3.1
- 2.
Agreement Reference (Articles) 11 **.
~"':Iii*:.
~.:I~'
Page No. 15 of 19 pages SAFEGUARDS EONflDENTIA~
- Estimated amount of nuclear material which has been lost.
Inspections Mode of routine inspections Intermittent.
Applicable formula and procedure for determination of maximum routine inspection effort:
Article 78(a) of the Agreement Actual inspection effort related to routine inspection activities The actual inspection effort will be determined by the Agency on the basis of the.relevant provisions of the Agreement to ensure the attainment of Agency safeguards objectives, assuming:
a)
Circumstances at the facility to be as described in the design information referred to in Code 2. above; b)
The continued validity of the information on the State System of accounting for and control of nuclear material, as set out in the General Part.
Indication of the scope of routine inspections under ordinary circumstances General:
- Examination of the records, verification for self-consistency;
- Comparison of reports and records for consistency.
At inventory KMPs
- Verification of the inventory by item counting, identification, integrity checks, non-destructive measurements.
- Application, examination and removal of Agency seals.
UNCLASSIFIED Text prepared on 198~9-24 Date of e~y into force:
1986-10--01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA Code: UXHF Code 7.4.3 7.4.4 7.4.5 7.5 7.6 7.7 General Part Reference Codes Agreement Reference (Articles) 7.'3:(d)
Page No. 16 of 19 pages SAFEGUARDS CONFIDENTIAL At flow KMPs Verification of inventory changes by item counting, identification, integrity checks, non-destructive measurements of fresh and irradiated fue 1.
- Application, examination and removal of Agency seals.
At strategic points for containment and surveillance
- Application, examination and removal of Agency seals; Servicing and maintenance of C/S instruments and devices; Observation of refuelling and spent fuel removal operations.
During interim verification of nuclear material inventory
- Item counting, identification, integrity checks,
.and NOA measurements (except material in core).
- Application, examination and removal of Agency seals.
Arrangements for the use by the Agency of equipment for independent measurement Specific arrangements for the use of equipment to be made as the need arises.
Persons to whom a request for any operation or for services at the facility should be addressed Vice President for Nuclear Public Service Electric and Gas Company Contacts at the facility Manager - Nuclear Fuel Nuclear Department Salem Nuclear Generating Station, Unit 1
Text prepared on e
Date of entry into force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility ~ode: UXHF I MBA Code: UXHF Code 7.8 7.8.1 General Part Reference Codes Agreement Reference (Articles)
Page No. 17 of 19 pages SAFESUARBS 60NFIBENTIAL Services and charges Inspection activities Charge
-' Observation of ongoing operational activities.
None
- Item counting and identification.
None
- Reading of instruments relevant to measurements connected with source and process data.
None NOA measurements:
a) Calibration of NOA instruments; None b)
Verification of NOA instruments calibration through the use of standards.
None c)
Agency NOA measurements.
None d)
Personnel and equipment for handling nuclear material during its measurement.
None
- Records:
Examination of records including reconciliation of records and reports and establishment of updated book inventory.
None
- Application, checking and removal of Agency seals.
None
- Surveillance :
Positioning, removal and use of Agency's surveillance devices.
None
- Lighting, including emergency lighting to light all critical areas under surveillance.
None
- Reviewing of surveillance records.
None
- Other charges.
Charges in connection with inspection activities not included above will be discussed as the situation arises.
Text prepared on 19Bti~?lASSIAED Date of e!y into force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility _Code: UXHF I MBA Code: UXHF Code 7.8.2 7.8.3 7.9 General Part Reference Codes Agreement Reference (Articles)
Page No. 18 of 19 pages SAFEGUARDS CONFIDENTIAL Services Health and safety (including e.g.
protective clothing, dosimeters).
None
- Office space.
None Power supply for IAEA instruments None
- Means of communication (telephone, telex, cable).
R
- Other services
- Facility personnel to escort the None Agency inspectors Mode of reimbursement of the expenses charged to the Agency By cheque after receipt of the invoice by the Agency.
Specific facility health and safety rules and regulations to be observed by Agency inspectors.
As specified in paragraph 54 of the Design Information ~uestionnaire.
- The Agency inspectors will be informed at the facility by short briefings at the time of entry into the facility of any changes in health and safety rules or ad hoc rules as might be required in view of a special situation that has occurred at the facility.
For health and safety reasons, inspectors will be escorted by qualified personnel.
R Costs to be reimbursed by the Agency.
- If any specific request by the Agency for services not covered above gives rise to expenses for which reimbursement is requested from the Agency, the Agency shall be notified of the expenses before the service is performed.
The Agency will only reimburse such expenses if it has confirmed its initial request and agreed in writing to the amount involved which it will reimburse.
Text prepared on 19Bi~?!A5SlflED Date of e~ into force:
1986-10-01 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF I MBA Code: UXHF Code
- 8.
8.1 8.2 General Part Reference Codes
~*
~* -*;,
Page No. 19 of 19 pages Agreement
~=~~~~~~:)
SAFEGUARDS CONFIDENTIAL 30,il~
Agency statements 88(a)
A summary statement will be made on the result of each inspection within 30 days of its completion.
88(b)
A statement on the conclusions the Agency has drawn from its verification activities in respect of the facility will be made within 60 days after the end of the month in which the Agency has verified the physical inventory.
The statement will include, as appropriate, conclusions drawn from:
(a) Records examination; (b) Reports to the Agency; (c) Examination of containment and surveillance results; (d) Verification of inventory changes; (e) Verification of material accountancy; (f) Verification of the quality and functioning of operator's measurement system.
(g) Activities in respect of MUF, shipper/receiver di fferen*ces and/or losses.